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Lawrence E. Hochreiter - Publications

Affiliations: 
Pennsylvania State University, State College, PA, United States 
Area:
Nuclear Engineering, Mechanical Engineering
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18 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2012 Lane JW, Aumiller DL, Hochreiter LE, Cheung FB. Three-field countercurrent flow limitation model Nuclear Technology. 177: 176-187. DOI: 10.13182/Nt12-A13364  0.567
2010 Lane JW, Aumiller DL, Cheung FB, Hochreiter LE. A self-consistent three-field constitutive model set for predicting co-current annular flow Nuclear Engineering and Design. 240: 3294-3308. DOI: 10.1016/J.Nucengdes.2010.06.013  0.517
2009 Narayanan S, Cheung F, Hochreiter L. Optimal Gap Size for Downward Facing Boiling and Steam Venting in a Hemispherical Annular Channel Nuclear Technology. 167: 178-186. DOI: 10.13182/Nt09-A8861  0.519
2008 Ergun S, Williams JG, Hochreiter LE, Wiersema H, Slootman M, Stempniewicz M. COBRA-TF Analysis of the High Flux Reactor Hot Channel for a Postulated Large-Break Loss-of-Coolant Accident Nuclear Technology. 163: 273-284. DOI: 10.13182/Nt08-A3987  0.736
2008 Lane JW, Hochreiter LE, Aumiller DL, Kushner RJ. Performance assessment of the two-phase pump degradation model in the RELAP5-3D transient safety analysis code Nuclear Technology. 161: 277-285. DOI: 10.13182/Nt08-A3926  0.441
2008 Ergun S, Hochreiter LE, Mahaffy JH. Modifications to COBRA-TF to model dispersed flow film boiling with two flow, four field Eulerian-Eulerian approach - Part 2 Annals of Nuclear Energy. 35: 1671-1676. DOI: 10.1016/J.Anucene.2008.02.014  0.768
2008 Ergun S, Hochreiter LE, Mahaffy JH. Modifications to COBRA-TF to model dispersed flow film boiling with two flow, four field Eulerian-Eulerian approach - Part 1 Annals of Nuclear Energy. 35: 1663-1670. DOI: 10.1016/J.Anucene.2008.02.013  0.776
2006 Ergun S, Williams JG, Hochreiter LE, Wiersema H, Slootman M, Stempniewicz M. Validation of COBRA-TF Critical Heat Flux Predictions for a Small-Hydraulic-Diameter Geometry Under Natural Boiling Conditions Nuclear Technology. 156: 69-74. DOI: 10.13182/Nt06-A3774  0.774
2005 Campbell RL, Cimbala JM, Hochreiter LE. Computational fluid dynamics prediction of grid spacer thermal-hydraulic performance with comparison to experimental results Nuclear Technology. 149: 49-61. DOI: 10.13182/Nt05-A3578  0.489
2003 Holowach MJ, Hochreiter LE, Mahaffy JH, Cheung FB. Modeling of droplet entrainment phenomena at a quench front International Journal of Heat and Fluid Flow. 24: 902-918. DOI: 10.1016/S0142-727X(03)00085-7  0.578
2003 Frepoli C, Mahaffy JH, Hochreiter LE. A moving subgrid model for simulation of reflood heat transfer Nuclear Engineering and Design. 224: 131-148. DOI: 10.1016/S0029-5493(03)00101-8  0.595
2003 Holowach MJ, Hochreiter LE, Cheung FB, Aumiller DL, Houser RJ. Scaling of quench front and entrainment-related phenomena Nuclear Engineering and Design. 223: 197-209. DOI: 10.1016/S0029-5493(03)00043-8  0.375
2002 Holowach MJ, Hochreiter LE, Cheung F, Aumiller DL. Critical Heat Flux During Reflood Transients in Small-Hydraulic-Diameter Geometries Nuclear Technology. 140: 18-27. DOI: 10.13182/Nt02-A3320  0.531
2002 Holowach MJ, Hochreiter LE, Cheung FB. A physical model for predicting annular film flow droplet entrainment in heat transfer systems Asme International Mechanical Engineering Congress and Exposition, Proceedings. 89-101. DOI: 10.1115/Imece2002-39279  0.599
2002 Sridharan A, Hochreiter LE, Cheung FB, Webb RL. Effect of chemical cleaning on steam generator tube performance Heat Transfer Engineering. 23: 38-47. DOI: 10.1080/014576302753249598  0.461
2002 Holowach MJ, Hochreiter LE, Cheung FB. A model for droplet entrainment in heated annular flow International Journal of Heat and Fluid Flow. 23: 807-822. DOI: 10.1016/S0142-727X(02)00194-7  0.598
1998 Zhang J, Bajorek SM, Kemper RM, Nissley ME, Petkov N, Hochreiter LE. Application of the W̱COBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis Nuclear Engineering and Design. 186: 279-301. DOI: 10.1016/S0029-5493(98)00279-9  0.513
1998 Young MY, Bajorek SM, Nissley ME, Hochreiter LE. Application of code scaling applicability and uncertainty methodology to the large break loss of coolant Nuclear Engineering and Design. 186: 39-52. DOI: 10.1016/S0029-5493(98)00217-9  0.428
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